Selective recovery equipment for sample water of pressurized water reactor nuclear power plant

Abstract

The utility model discloses selective sample water recovery equipment for a pressurized water reactor nuclear power plant. The selective sample water recovery equipment comprises a mounting rack below a nuclear sampling system, and a sample water recovery device and a sample water discharge device which are mounted on the mounting rack, the sample water recovery device comprises a water collection tank pipe, and a water drainage connector is arranged on the water collection tank pipe; and the sample water discharge device comprises a drain pipe, a connecting flange and a discharge interface. Under normal working conditions, sample water discharged by the nuclear sampling system is discharged to the water collecting tank pipe through the tail end of the pipeline, and the sample water is collected by the water collecting tank pipe and then conveyed to the sample recycling box of the nuclear sampling system. Under special working conditions, the tail end of a sample water pipeline of a nuclear sampling system is introduced into the inner cavity of the connecting flange, and sample water passes through the drain pipe and is discharged to a waste liquid treatment system from the discharge interface. The problem that the water quality of the whole pressurized water reactor secondary loop can be polluted due to recovery of polluted sample water under a special working condition is solved, and the beneficial effects of environmental protection, cost reduction, efficiency improvement, high yield and the like can be brought by wastewater recovery under a normal working condition.

Description

TECHNICAL FIELD

[0001] The utility model relates to nuclear power technology field especially relates to a pressurized water reactor nuclear power plant sample water selective recovery equipment. BACKGROUND

[0002] The pressurized water reactor nuclear power plant steam generator carries out continuous blowdown through the steam generator blowdown water system (APG) under different working conditions to keep the water quality of the steam generator secondary side meet the requirements and collect and treat the steam generator blowdown water. The unqualified water quality of the secondary loop side can cause equipment accelerated corrosion (especially the steam generator) and damage to the loop integrity. If the unqualified feed water corrodes the steam generator U-shaped tube, it will cause the leakage from the primary side to the secondary side, so the water quality of the secondary loop is purified through the continuous blowdown of the steam generator. The treated blowdown water is sampled and analyzed to be qualified in water quality, and is sent to the condenser of the unit for continuous use. The part of the water introduced into the nuclear sampling system (REN) is divided into recycled water samples (KRT channel, conductivity meter, sampling pipe safety valve take-off drainage) and non-recycled water samples (online sodium meter, pH meter, manual sampling), the former is recycled to the secondary loop through the sample recycling tank, and the latter is finally discharged to the ground waste water of the waste liquid treatment system (TEU system). A nuclear power unit generates about 15m 3 of waste liquid per day, and needs to discharge a tank of waste liquid treatment system ground waste liquid storage tank waste liquid (50m 3 ) about every 3 days, about 120 tanks per year, which increases a large amount of waste water discharge work, and a single unit generates about 3000 cubic meters of waste water per year, causing waste of water resources and increasing the water production cost of the power plant.

[0003] The experimental data analysis statistics show that the pH value of the sample water is about 9.6, the pH value of the waste water discharged by the waste liquid treatment system is required to be controlled at 6-9, so the sample water discharged to the waste liquid treatment system is easy to cause the pH value of the waste water discharged by the waste liquid treatment system to be unqualified, which brings a large amount of dosing, sampling analysis and discharge operation workload to the chemical and operation personnel and increases the cost of using the acid-base neutralization reagent of the waste liquid treatment system;

[0004] In addition, the system water lost by the pressurized water reactor secondary loop needs to be additionally supplemented through the conventional island desalination distribution system (SER), which increases the water production cost and also causes loss of steam turbine thermal efficiency, affects the normal electric power of the unit and the power generation capacity of the unit, and relates to the production benefit of the nuclear power plant.

[0005] The defects of the original sample water discharge mode mainly include:

[0006] In the traditional method, sample water is collected in sections and discharged to a waste liquid treatment system, which increases the amount of waste liquid discharged and is not environmentally friendly. The sample water discharge method in the traditional method is not selective, and cannot confirm whether to recover according to the water quality condition, and cannot match the water demand brought by the actual working condition. The traditional method wastes 3000 square meters of desalted water per unit per year, which increases the cost of water production of the power plant and is not environmentally friendly. The pH of the sample water discharged to the waste liquid treatment system in the traditional method is different from the control standard of the waste liquid treatment system, and the pH value needs to be adjusted by adding chemicals, which increases the workload of on-site chemical addition and sampling analysis, and causes waste liquid discharge pressure. The traditional method will cause the loss of steam turbine thermal efficiency, affect the normal electric power of the unit, and affect the power generation capacity of the unit, which relates to the production benefit of the nuclear power plant. Practical new type content

[0007] The technical problem to be solved by the utility model is to provide a sample water selective recovery equipment for a pressurized water reactor nuclear power plant.

[0008] The utility model adopts the technical scheme in the technical problem thereof: construct a sample water selective recovery equipment for a pressurized water reactor nuclear power plant, including the mounting bracket below the nuclear sampling system, and the sample water recovery device and sample water discharge device mounted on the mounting bracket.

[0009] The sample water recovery device includes a water collecting groove pipe, and at least one water discharge interface for connecting a sample recovery box of the nuclear sampling system is arranged on the water collecting groove pipe.

[0010] The sample water discharge device includes at least one drain pipe, a plurality of connecting flanges for connecting the nuclear sampling system are arranged on the drain pipe, and at least one discharge interface for connecting the waste liquid treatment system is further arranged on the drain pipe.

[0011] In some embodiments, the bottom of the water collecting groove pipe is inclined downward from both sides to the middle part, and at least one water discharge interface is arranged at the bottom position of the water collecting groove pipe.

[0012] In some embodiments, a filter is arranged on the water collecting groove pipe.

[0013] In some embodiments, a plurality of reinforcing rib plates are arranged in the water collecting groove pipe, the reinforcing rib plates are arranged in the length direction of the water collecting groove pipe at intervals, each reinforcing rib plate is connected to the two side walls in the width direction of the water collecting groove pipe, and the bottom of the reinforcing rib plate is arranged at intervals with the inner bottom of the water collecting groove pipe.

[0014] In some embodiments, the inlet of the connecting flange is arranged upward.

[0015] In some embodiments, the sample water discharge device further includes a flange cover plate detachably connected with the connecting flange.

[0016] In some embodiments, the number of the connecting flanges is four.

[0017] In some embodiments, the number of the mounting racks is multiple, and the multiple mounting racks are arranged along the length direction of the water collecting groove pipe.

[0018] In some embodiments, each of the mounting racks comprises two support beams arranged in parallel, a cross beam connecting upper ends of the two support beams, a first bearing beam and a second bearing beam respectively connecting middle portions of the two support beams, and the first bearing beam is above the second bearing beam, the water collecting groove pipe is arranged on the first bearing beam, and the drain pipe is arranged on the second bearing beam.

[0019] In some embodiments, the drain pipe is fixedly connected with the second bearing beam through a pipe clamp.

[0020] The water pressurized nuclear power plant sample water selective recovery equipment has the following beneficial effects: the water pressurized nuclear power plant sample water selective recovery equipment comprises a mounting rack below a nuclear sampling system, and a sample water recovery device and a sample water discharge device mounted on the mounting rack; the sample water recovery device comprises a water collecting groove pipe, and at least one water discharge interface for connecting a sample recovery box of the nuclear sampling system is arranged on the water collecting groove pipe; the sample water discharge device comprises at least one drain pipe, a plurality of connecting flanges for connecting the nuclear sampling system are arranged on the drain pipe, and at least one discharge interface for connecting a waste liquid treatment system is further arranged on the drain pipe. Under normal conditions, sample water discharged by the nuclear sampling system is discharged to the water collecting groove pipe through the pipeline end, and the sample water collected by the water collecting groove pipe is transmitted to the sample recovery box of the nuclear sampling system. Under special conditions, the sample water pipeline end of the nuclear sampling system is introduced into the inner cavity of the connecting flange, and the sample water is discharged to the waste liquid treatment system through the discharge interface of the drain pipe.

[0021] The water pressurized nuclear power plant sample water selective recovery equipment solves the problem that the recovery of contaminated sample water may cause the entire water quality of the water pressurized secondary loop to be contaminated under special conditions, and can bring the beneficial effects of environmental protection, cost reduction, efficiency increase, high income and the like under normal conditions. BRIEF DESCRIPTION OF DRAWINGS

[0022] In order to more clearly illustrate the technical scheme of the present application, the following will further illustrate the present application with reference to the drawings and embodiments. It should be understood that the following drawings only show some embodiments of the present application, and therefore should not be regarded as a limitation on the scope. For those skilled in the art, other related drawings can also be obtained without creative labor. In the drawings:

[0023] Figure 1is the application diagram of the water selective recovery equipment of the pressurized water reactor nuclear power plant in some embodiments of the utility model;

[0024] Figure 2 is the structure diagram of the water selective recovery equipment of the pressurized water reactor nuclear power plant in some embodiments of the utility model;

[0025] Figure 3 is Figure 2 the sectional view along A-A line of the water selective recovery equipment of the pressurized water reactor nuclear power plant in some embodiments of the utility model;

[0026] Figure 4 is Figure 2 the sectional view along B-B line of the water selective recovery equipment of the pressurized water reactor nuclear power plant in some embodiments of the utility model;

[0027] Figure 5 is Figure 2 the sectional view along C-C line of the water selective recovery equipment of the pressurized water reactor nuclear power plant in some embodiments of the utility model;

[0028] Figure 6 is the partial structure diagram of the water collecting tank pipe in some embodiments of the utility model. DETAILED DESCRIPTION

[0029] In order to have a clearer understanding of the technical features, purposes and effects of the utility model, the specific embodiments of the utility model will be described in detail with reference to the drawings. In the following description, it should be understood that the directions or position relations indicated by "front", "back", "upper", "lower", "left", "right", "vertical", "horizontal", "vertical", "horizontal", "top", "bottom", "inner", "outer", "head", "tail" and the like are based on the directions or position relations shown in the drawings, the specific directions are constructed and operated, and are only for the convenience of describing the technical scheme, and cannot be understood as indicating that the devices or elements indicated must have the specific directions, therefore, it cannot be understood as the limitation of the utility model.

[0030] It should be noted that, unless otherwise explicitly specified and limited, the terms "mounting", "connecting", "connecting", "fixing", "setting" and the like should be understood in a broad sense, for example, it can be fixedly connected, or it can be detachably connected, or it can be integrated; it can be mechanically connected, or it can be electrically connected; it can be directly connected, or it can be indirectly connected through an intermediate medium, or it can be the internal communication of two elements or the interaction relationship between two elements. When an element is referred to as "on" or "below" another element, the element can be "directly" or "indirectly" above the other element, or there can be one or more intervening elements. The terms "first", "second", "third" and the like are only for the convenience of describing the technical solutions, and cannot be understood as indicating or implying relative importance or implicitly indicating the number of indicated technical features. Therefore, the features with "first", "second", "third" and the like can be explicitly or implicitly included one or more of the features. For those skilled in the art, the specific meaning of the above terms in the present application can be understood according to the specific circumstances.

[0031] In the following description, specific details are set forth such as specific system structures, techniques, etc. in order to provide a thorough understanding of the embodiments of the present application for purposes of explanation and not of limitation. However, it will be apparent to those skilled in the art that the present application can be realized in other embodiments without these specific details. In other cases, detailed descriptions of well-known systems, devices, circuits, and methods are omitted so as not to obscure the description of the present application with unnecessary details.

[0032] Referring to Figures 1 to 5 The utility model discloses a kind of pressurized water reactor nuclear power plant sample water selective recovery equipment, which includes the mounting bracket 10 below nuclear sampling system 100, and sample water recovery device 20 and sample water discharge device 30 installed on mounting bracket 10. The nuclear sampling system 100 can include manual sampling module 101, online sodium table module 102, online pH table module 103 and online electric conductivity table module 104.

[0033] The sample water recovery device 20 includes a water collecting tank pipe 21, which is arranged below the nuclear sampling system 100, and the opening of the water collecting tank pipe 21 is arranged upward, i.e. towards the nuclear sampling system 100. The water collecting tank pipe 21 is provided with at least one water discharge interface 22 for connecting a nuclear sampling system sample recovery tank 200. Under normal conditions, the sample water discharged by the nuclear sampling system 100 is discharged to the water collecting tank pipe 21 through the pipe end, and then transmitted to the nuclear sampling system sample recovery tank 200 after collection.

[0034] The sample water discharge device 30 comprises at least one drain pipe 31, the drain pipe 31 is provided with a plurality of connecting flanges 32 for connecting with the nuclear sampling system 100, and the drain pipe 31 is further provided with at least one discharge interface 33 for connecting with the waste liquid treatment system 300. When the special working condition, the sample water pipe of the nuclear sampling system 100 is introduced into the inner cavity of the connecting flange 32, and the sample water is discharged from the discharge interface 33 to the waste liquid treatment system 300 through the drain pipe 31.

[0035] In some embodiments, the water collecting tank pipe 21 can be a substantially rectangular tubular structure, the longitudinal section of the water collecting tank pipe 21 is also substantially rectangular, the inner cavity of the water collecting tank pipe 21 forms a water collecting tank, and the bottom of the water collecting tank pipe 21 is inclined downward to the middle part on both sides, and at least one drain interface 22 is arranged at the bottom position of the water collecting tank pipe 21. For example, the drain interface 22 can be connected with the bottom surface of the bottom position of the water collecting tank pipe 21, or the drain interface 22 can be connected with the side surface of the bottom position of the water collecting tank pipe 21. The drain interface 22 can be a flange interface, or the drain interface 22 can be a drain pipe, and a control valve can be arranged on the drain pipe.

[0036] Preferably, the bottom of the water collecting tank pipe 21 is inclined downward to the middle part on both sides, and the sample water can flow into the drain interface 22 naturally by gravity, without causing liquid accumulation and overflow. Further, the angle between the bottom of the water collecting tank pipe 21 and the horizontal plane is an acute angle, for example, it can be 3°, 4°, 5°, or it can be 10°, 20°, and the angle can be selected according to actual needs, which is not limited here.

[0037] As shown in Figure 3 some embodiments, the water collecting tank pipe 21 is provided with a filter 23, which can be a sieve plate or a filter screen.

[0038] As shown in Figure 6 some embodiments, the water collecting tank pipe 21 is provided with a plurality of reinforcing rib plates 24, the reinforcing rib plates 24 are arranged in the length direction of the water collecting tank pipe 21 and are spaced apart, each reinforcing rib plate 24 connects the two side walls of the water collecting tank pipe 21 in the width direction, and the bottom of the reinforcing rib plate 24 is spaced apart from the inner bottom of the water collecting tank pipe 21, so that the sample water can flow in the water collecting tank pipe 21, and the upper surface of the reinforcing rib plate 24 can be spaced apart from the upper surface of the water collecting tank pipe 21, and the filter 23 can be placed on the reinforcing rib plate 24. Understandably, the reinforcing rib plate 24 can improve the overall structural strength of the water collecting tank pipe 21, and can also serve as a support structure for the filter 23.

[0039] In some embodiments, the water collecting tank pipe 21, the drain interface 22, the filter 23, and the reinforcing rib plate 24 can all be made of metal materials, which include but are not limited to stainless steel.

[0040] In some embodiments, the hydrophobic pipe 31 can be a whole pipe structure, or the hydrophobic pipe 31 can be a multi-segment pipe, and adjacent pipes are detachably connected through flanges.

[0041] In some embodiments, the inlet of the connection flange 32 is upwardly arranged, i.e., arranged toward the nuclear sampling system 100. The sample water pipe of the nuclear sampling system 100 can be connected to the inlet of the connection flange 32 through a connecting pipe for water drainage. The connecting pipe includes but is not limited to a plastic hose.

[0042] In some embodiments, the sample water drainage device 30 further comprises a flange cover plate 34 detachably connected to the connection flange 32, which can be detachably connected through bolt connection. When the sample water drainage device 30 or the individual connection flange 32 is not needed, the flange cover plate 34 can be installed on the connection flange 32 to seal the connection flange 32, so as to prevent impurities from entering the hydrophobic pipe 31. When the flange cover plate of the sample water drainage device is opened under special conditions, the end of the sample water pipe of the nuclear sampling system 100 is introduced into the inner cavity of the connection flange 32, the end of the sample water pipe is introduced into the inner cavity of the connection flange 32 through the connecting pipe, and the sample water is discharged from the drainage interface 33 to the waste liquid treatment system 300 through the hydrophobic pipe 31.

[0043] In some embodiments, the number of connection flanges 32 is four. Of course, the four connection flanges 32 can be correspondingly arranged below the manual sampling module 101, the online sodium meter module 102, the online pH meter module 103, and the online conductivity meter module 104, so as to facilitate corresponding connection and save the length of the connecting pipe. Of course, the number and position of the connection flanges 32 can be selected according to actual needs, which are not limited here.

[0044] In some embodiments, the drainage interface 33 can be a flange interface, or the drainage interface 33 can be a drainage pipe, and a control valve can be arranged on the drainage pipe.

[0045] In some embodiments, the hydrophobic pipe 31, the connection flange 32, the drainage interface 33, and the flange cover plate 34 can all be made of metal materials, which include but are not limited to stainless steel.

[0046] In combination Figures 2 to 5 In some embodiments, the number of mounting racks 10 is multiple, and the multiple mounting racks 10 are arranged along the length direction of the water collecting groove pipe 21 to better achieve support. In some embodiments, the mounting rack 10 can be made of metal materials, which include but are not limited to stainless steel.

[0047] In some embodiments, each mounting bracket 10 includes a support beam 11, a crossbeam 12, a first load-bearing beam 13, and a second load-bearing beam 14. There are two support beams 11, which are arranged in parallel relative to each other. The crossbeam 12 connects the upper ends of the two support beams 11. The first load-bearing beam 13 and the second load-bearing beam 14 are respectively connected to the middle of the two support beams 11, and the first load-bearing beam 13 is located above the second load-bearing beam 14. A water collection tank pipe 21 is provided on the first load-bearing beam 13, and a drainage pipe 31 is provided on the second load-bearing beam 14.

[0048] In some embodiments, the drainage pipe 31 is fixedly connected to the second supporting beam 14 via a pipe clamp 15 (e.g., Figure 5 (As shown).

[0049] Understandably, based on the pipeline layout and plant space arrangement of the nuclear sampling system (REN) in a pressurized water reactor nuclear power plant, the secondary side sample water rack of the REN system is designed and modified. A design is implemented whereby, under normal operating conditions, the water introduced into the REN from the steam generator wastewater system (APG) (KRT channel, conductivity meter, sampling pipe safety valve opening and drainage, online sodium meter, pH meter, manual sampling) is entirely recycled to the REN sample recovery tank 200 via the collection tank pipe 21 covered by filter element 23. Under special operating conditions (seawater leakage, steam generator pipeline rupture, etc.), the sample water may be severely contaminated. In this case, it is discharged through the sample water discharge device 30 to the waste liquid treatment system 300 for treatment and discharge to prevent the spread of pollution.

[0050] The selective sample water recovery equipment for pressurized water reactor nuclear power plants solves the problem that the recovery of contaminated sample water under special operating conditions may lead to the contamination of the water quality in the secondary loop of the pressurized water reactor. Under normal operating conditions, wastewater recovery can bring beneficial effects such as environmental protection (saving 3,000 cubic meters of demineralized water per unit), cost reduction (reducing water production costs), efficiency improvement (improving on-site work efficiency and optimizing the workload of wastewater discharge from the waste liquid treatment system), and high returns (reducing turbine thermal efficiency loss, increasing unit electrical power, and increasing unit power generation).

[0051] 1. The sample water treatment method is more adapted to actual operating conditions. Based on unit experience, the probability of sample water being contaminated and the unit experiencing special operating conditions is extremely low. The design allows for selective recovery of sample water, which solves the problem that the recovery of contaminated sample water under special operating conditions may lead to contamination of the entire pressurized water reactor secondary circuit, while also achieving the various benefits of sample water recovery under normal operating conditions.

[0052] 2. Sample water recycling reduces costs and increases efficiency. It reduces wastewater discharge and lowers wastewater treatment costs. By demonstrating sample recycling methods and pathways, an innovative approach was developed to collect sample water in a collection tank and then recycle it by gravity, eliminating the need for additional power equipment and preventing the waste of high-quality demineralized water. Each unit saves 3,000 cubic meters of demineralized water annually.

[0053] 3. Improve quality and efficiency, and reduce the burden on on-site personnel. The pH of the sample water discharged into the wastewater treatment system (TEU) by traditional methods is different from the control standard of the TEU system. It is necessary to add chemicals to adjust the pH value, which increases the workload of on-site chemical addition and sampling analysis, and also puts pressure on wastewater discharge.

[0054] 4. Increase unit power output and generate revenue for the power plant. Water recycling reduces turbine thermal efficiency losses, increases unit power output, and boosts power generation, thus contributing to the company's revenue.

[0055] In the description of this specification, the references to terms such as "one embodiment," "some embodiments," "example," "specific example," or "some examples," etc., indicate that a specific feature, structure, material, or characteristic described in connection with that embodiment or example is included in at least one embodiment or example of the present invention. In this specification, the illustrative expressions of the above terms do not necessarily refer to the same embodiment or example. Furthermore, the specific features, structures, materials, or characteristics described may be combined in any suitable manner in one or more embodiments or examples. Moreover, without contradiction, those skilled in the art can combine and integrate the different embodiments or examples described in this specification, as well as the features of different embodiments or examples.

Claims

1. A selective recovery device for sample water from a pressurized water reactor nuclear power plant, characterized in that, Includes a mounting frame (10) below the nuclear sampling system (100), and a sample water recovery device (20) and a sample water discharge device (30) mounted on the mounting frame (10); The sample water recovery device (20) includes a water collection tank pipe (21), which is provided with at least one drain port (22) for connecting to the sample recovery box (200) of the nuclear sampling system; The sample water discharge device (30) includes at least one drain pipe (31), which is provided with a plurality of connecting flanges (32) for connecting to the nuclear sampling system (100), and the drain pipe (31) is also provided with at least one discharge port (33) for connecting to the waste liquid treatment system (300).

2. The selective recovery equipment for sample water from a pressurized water reactor nuclear power plant according to claim 1, characterized in that, The bottom of the water collection trough pipe (21) is inclined downwards from both sides towards the middle, and at least one of the drainage interfaces (22) is located at the bottom of the water collection trough pipe (21).

3. The selective recovery equipment for sample water from a pressurized water reactor nuclear power plant according to claim 1, characterized in that, The water collection tank pipe (21) is equipped with a filter element (23).

4. The selective recovery equipment for sample water from a pressurized water reactor nuclear power plant according to claim 1, characterized in that, The water collection trough pipe (21) is provided with a plurality of reinforcing ribs (24), which are spaced apart along the length of the water collection trough pipe (21). Each reinforcing rib (24) is connected to the two side walls of the water collection trough pipe (21) in the width direction, and the bottom of the reinforcing rib (24) is spaced apart from the inner bottom of the water collection trough pipe (21).

5. The selective recovery equipment for sample water from a pressurized water reactor nuclear power plant according to claim 1, characterized in that, The inlet of the connecting flange (32) is facing upward.

6. The selective recovery equipment for sample water from a pressurized water reactor nuclear power plant according to claim 1, characterized in that, The sample water discharge device (30) also includes a flange cover plate (34) that is detachably connected to the connecting flange (32).

7. The selective recovery equipment for sample water from a pressurized water reactor nuclear power plant according to claim 1, characterized in that, The number of connecting flanges (32) is four.

8. The selective recovery equipment for sample water from a pressurized water reactor nuclear power plant according to claim 1, characterized in that, The number of mounting brackets (10) is multiple, and the multiple mounting brackets (10) are spaced apart along the length direction of the water collection tank pipe (21).

9. The selective recovery equipment for sample water from a pressurized water reactor nuclear power plant according to claim 1, characterized in that, Each mounting bracket (10) includes a support beam (11), a crossbeam (12), a first load-bearing beam (13), and a second load-bearing beam (14). There are two support beams (11), which are arranged in parallel relative to each other. The crossbeam (12) connects the upper ends of the two support beams (11). The first load-bearing beam (13) and the second load-bearing beam (14) are respectively connected to the middle of the two support beams (11), and the first load-bearing beam (13) is located above the second load-bearing beam (14). The water collection tank pipe (21) is located on the first load-bearing beam (13), and the drainage pipe (31) is located on the second load-bearing beam (14).

10. The selective recovery equipment for sample water from a pressurized water reactor nuclear power plant according to claim 9, characterized in that, The drainage pipe (31) is fixedly connected to the second bearing beam (14) by a pipe clamp (15).

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